Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor

@article{Liu2020CoreTE,
  title={Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor},
  author={Xiao Liu and Ran Zhang and Yu Liang and Simiao Tang and Chenglong Wang and Wenxi Tian and Zhuohua Zhang and Suizheng Qiu and Guanghui Su},
  journal={Annals of Nuclear Energy},
  year={2020},
  volume={142},
  pages={107412}
}

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